Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods

被引:0
|
作者
Mitkov, S. [1 ]
Spasov, I [2 ]
Kolev, N. P. [1 ]
机构
[1] Tech Univ Sofia, Inst Nucl Res & Nucl Energy, BAS, 72 Tsarigradsko Chaussee, Sofia 1784, Bulgaria
[2] Tech Univ Sofia, 8 Kliment Ohridski, Sofia 1756, Bulgaria
关键词
DEPARTURE; CODE;
D O I
10.3139/124.110910
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A hypothetical main steam line break transient in a VVER-1000 core with multiple equipment faults was simulated with the coupled COBAYA4/CTF and COBAYA3/FLICA4 nodal core models. The objective was to test recent versions of the models developed in the EU NURISP and NURESAFE projects and to analyze the thermal-hydraulic conditions in the hot assembly at the pin-cell level. The accident scenario was specified as an aggravated variant of the OECD/NEA VVER-1000 MSLB benchmark with eight peripheral control rod clusters stuck out of the core after scram, all of them in the over-cooled sector. Coarse-mesh models and a realistic cross-section library were used to compute the full-core behavior with pre-calculated MSLB boundary conditions and to identify the hot assembly. Then a sub-channel thermal-hydraulic analysis of the hot assembly was performed with the CTF code, using time-dependent assembly boundary conditions from the coarse-mesh vessel and core simulation. The results show that the predicted values of the safety parameters do not exceed the safety limits.
引用
收藏
页码:389 / 395
页数:7
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